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Volume 155

Number 1

Hydrogen Production Using High-Temperature Steam Electrolysis Supported by Advanced Gas Reactors with Supercritical CO2 Cycles

Bilge Yildiz, Katherine J. Hohnholt, Mujid S. Kazimi

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 1-21

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3742

Evaluation of the Impact of SAMG on the Level-2 PSA Results of a Pressurized Water Reactor

Yu-Chih Ko, Ching-Hui Wu, Min Lee

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 22-33

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3743

Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle

T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N. Hill, M. Salvatores, P. J. Finck

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 34-54

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3744

Evaluation of Long-Life Transuranics Breakeven and Burner Cores for Waste Minimization in a PB-GCFR Fuel Cycle

T. A. Taiwo, E. A. Hoffman, R. N. Hill, W. S. Yang

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 55-66

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3745

Feasibility Study on Transient Identification in Nuclear Power Plants Using Support Vector Machines

Christoffer Gottlieb, Vasily Arzhanov, Waclaw Gudowski, Ninos Garis

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 67-77

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3746

Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 78-89

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3747

Thermal Design of an Alternative Boiling Water Reactor Spent Nuclear Fuel Package for Yucca Mountain Repository

P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 90-104

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3748

Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant

Norihisa Saito, Yumiko Tsuchiya, Seiji Yamamoto, Yoshie Akai, Tadasu Yotsuyanagi, Masafumi Domae, Yosuke Katsumura

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 105-113

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3749

Chronic Dose Due to a Continuous Tritium Release Calculated by CAP88-PC and NORMTRI

Stacey F. Imboden, Thomas J. Overcamp

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 114-118

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT06-A3750

 
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